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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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July 2025
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Dirk Wilhelm, Leonhard Meyer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 162-172
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33717
Articles are hosted by Taylor and Francis Online.
The flow dynamics in the upper core structure (UCS) during the expansion phase of a liquid-metal fast breeder reactor core disruptive accident were investigated experimentally and numerically. A simulant material experiment was designed to verify some of the thermal-hydraulic models in SIMMER-II. The experiments showed the large effect of the heat transfer in the UCS and the relatively small effect of friction. The reduction of the work potential of the expanding fuel by the presence of the UCS is shown as a function of the initial pressure and the temperature difference between the core and the UCS, both for simulant materials and UO2 fuel. It is described how the experimental data can be extrapolated to prototypical conditions, which phenomena modeled in the code predictions of SIMMER-II are different for simulant and prototypical transients, and how the experimental results compare to effects of prototypical phenomena that could not be modeled in the experiment.
